# openmc.deplete.helpers.ChainFissionHelper¶

class openmc.deplete.helpers.ChainFissionHelper[source]

Computes normalization using fission Q values from depletion chain

Variables
prepare(chain_nucs, rate_index)[source]

Populate the fission Q value vector from a chain.

Parameters
• chain_nucs (iterable of openmc.deplete.Nuclide) – Nuclides used in this depletion chain. Do not need to be ordered

• rate_index (dict of str to int) – Dictionary mapping names of nuclides, e.g. "U235", to a corresponding index in the desired fission Q vector.

update(fission_rates)[source]

Update energy produced with fission rates in a material

Parameters

fission_rates (numpy.ndarray) – fission reaction rate for each isotope in the specified material. Should be ordered corresponding to initial rate_index used in prepare()